Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions Ahmad Pirouzmand * , Peyman Dehghani, Kamal Hadad, Mohammadreza Nematollahi Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran article info Article history: Received 5 January 2015 Received in revised form 6 May 2015 Accepted 9 June 2015 Available online xxx Keywords: Radioactive material dispersion Dose assessment BNPP-1 LBLOCA Gaussian plume dispersion model abstract Assessment of individual and collective doses around the unit-1 of Bushehr nuclear power plant (BNPP-1) site during normal nuclear reactor operation and under reactor accident conditions which are essential for safety and environmental analyses is presented in this paper. Release of radioactive materials to the environment following a design basic acci- dent (DBA) (e.g. LBLOCA) is evaluated using HOTSPOT health physics computer code. In the normal operation conditions, atmospheric dispersion of radioactive material is calculated using CAP88-PC code. These codes utilize a Gaussian dispersion air transport plume model to simulate the atmospheric dispersion of radionuclides in different atmospheric stability classes and various wind speeds and directions. To calculate the doses under normal operation using CAP88 code, the surrounding area of the BNPP-1 within a radius of 30 km is gridded into 12 concentric rings and 16 sectors and the distribution of population and data of agricultural products are calculated for each grid. The meteorological data on atmo- spheric stability conditions, wind speed and the frequency distribution of wind direction based on data collected near the reactor site are also analyzed and applied. The results illustrate that the maximum total effective dose equivalent (TEDE) and committed effective dose equivalent (CEDE) values for personnel and public around the BNPP-1 site are lower than the annual effective dose limits for workers and public in normal operation and under accident conditions. Also, the results of the radiological impacts of the BNPP-1 in normal and accidental radioactive materials releases are compared with the dose values given in the Final Safety Analysis Report (FSAR) of the BNPP-1. Copyright © 2015, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved. Introduction One of the most crucial safety and health physics concerns in research and power nuclear reactors is the radioactive material release around the nuclear reactor site. Due to the unavoidable presence of personnel within the reactor site and the population outside the site, the release should be moni- tored frequently and properly for both normal operation and * Corresponding author. Tel./fax: þ98 71 36473474. E-mail address: pirouzm@shirazu.ac.ir (A. Pirouzmand). Available online at www.sciencedirect.com ScienceDirect journal homepage: www.elsevier.com/locate/he international journal of hydrogen energy xxx (2015) 1 e8 http://dx.doi.org/10.1016/j.ijhydene.2015.06.043 0360-3199/Copyright © 2015, Hydrogen Energy Publications, LLC. Published by Elsevier Ltd. All rights reserved. Please cite this article in press as: Pirouzmand A, et al., Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions, International Journal of Hydrogen Energy (2015), http://dx.doi.org/10.1016/ j.ijhydene.2015.06.043